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| Attachment 2 | | Attachment 2 |
| * May 13,1996 Page 2 We have determined that, heavy loads are handled as described in the correspondence between the NRC and NSP in response to the December 22,1980 letter from Darrell Eisenhut, Director of Licensing, NRR, to all licensees of operating plants, titled " Control of Heavy Loads" with two notable differences. | | * May 13,1996 Page 2 We have determined that, heavy loads are handled as described in the correspondence between the NRC and NSP in response to the {{letter dated|date=December 22, 1980|text=December 22,1980 letter}} from Darrell Eisenhut, Director of Licensing, NRR, to all licensees of operating plants, titled " Control of Heavy Loads" with two notable differences. |
| : 1. The Prairie Island auxiliary building crane was upgraded to meet the single-failure-proof criteria of Section 5.1.6 and Appendix C of NUREG-0612 in anticipation of handling spent fuel dry storage casks. Prior to handling the first dry storage cask, submittals to the NRC in support of Technical Specification changes regarding the use of the upgraded crane were made (see details starting on page 3). | | : 1. The Prairie Island auxiliary building crane was upgraded to meet the single-failure-proof criteria of Section 5.1.6 and Appendix C of NUREG-0612 in anticipation of handling spent fuel dry storage casks. Prior to handling the first dry storage cask, submittals to the NRC in support of Technical Specification changes regarding the use of the upgraded crane were made (see details starting on page 3). |
| : 2. A construction gantry crane can be temporarily installed for the purpose of installing or removing temporary spent fuel storage racks in Pool #1. The heavy load handling considerations utilizing this crane has been discussed in docketed correspondence with respect to a fuel pool re-rack modification. This correspondence occurred at roughly the same time period as that of the generic heavy load issue discussions. Since, at the time, this crane was thought of as temporary (just to be used during these modifications) it was never considered during our responses to the generic issues. In fact, the temporary racks were removed once using this crane and utilizing the heavy loads handling process reviewed by the NRC for the re-rack project. Also, the racks were installed and removed once using the upgraded auxiliary building crane. During this evolution, the rack movements were controlled by procedures which met heavy loads handling generic requirements but the rack movements have not been incorporated into the formal plant heavy loads handling program. Therefore, we need to determine the compliance of our use of the gantry crane with all aspects of NUREG-0612 and incorporate these potential movements into the plant heavy loads handling program. We will ensure compliance with NUREG-0612, Section 5.1 pnor to the next use of the gantry crane within the spent fuelpool enclosure or submit correspondence detailing any necessary exception and its basis. | | : 2. A construction gantry crane can be temporarily installed for the purpose of installing or removing temporary spent fuel storage racks in Pool #1. The heavy load handling considerations utilizing this crane has been discussed in docketed correspondence with respect to a fuel pool re-rack modification. This correspondence occurred at roughly the same time period as that of the generic heavy load issue discussions. Since, at the time, this crane was thought of as temporary (just to be used during these modifications) it was never considered during our responses to the generic issues. In fact, the temporary racks were removed once using this crane and utilizing the heavy loads handling process reviewed by the NRC for the re-rack project. Also, the racks were installed and removed once using the upgraded auxiliary building crane. During this evolution, the rack movements were controlled by procedures which met heavy loads handling generic requirements but the rack movements have not been incorporated into the formal plant heavy loads handling program. Therefore, we need to determine the compliance of our use of the gantry crane with all aspects of NUREG-0612 and incorporate these potential movements into the plant heavy loads handling program. We will ensure compliance with NUREG-0612, Section 5.1 pnor to the next use of the gantry crane within the spent fuelpool enclosure or submit correspondence detailing any necessary exception and its basis. |
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| Attachment 2 | | Attachment 2 |
| ! , . May 13,1996 Page 4 Details regarding the upgraded auxiliary building crane follow: | | ! , . May 13,1996 Page 4 Details regarding the upgraded auxiliary building crane follow: |
| Prairie Island Cask Handling System j Design in preparation for the dry cask storage project, the Prairie Island auxiliary building crane was upgraded in 1992 to meet the single-failure-proof criteria of Section 5.1.6 and Appendix C of NUREG-0612. The upgrade involved replacement the existing trolley structure and hoist with an Ederer, Inc. designed trolley and hoist. The Ederer single-failure-proof design is described in Revision 3, Amendment 3, to Generic Licensing topical Report EDR-1(P)-A, "Ederer Nuclear Safety-Related Extra Safety and monitoring (X-SAM) Cranes", dated October 8,1982. The report describes the design and testing of the single-failure-proof features which are included in Ederer's X-SAM cranes intended for handling spent fuel casks and other safety related loads in a nuclear power plant. NRC staff approval of the report was documented in a Safety Evaluation transmitted by NRC letter dated August 26,1983. | | Prairie Island Cask Handling System j Design in preparation for the dry cask storage project, the Prairie Island auxiliary building crane was upgraded in 1992 to meet the single-failure-proof criteria of Section 5.1.6 and Appendix C of NUREG-0612. The upgrade involved replacement the existing trolley structure and hoist with an Ederer, Inc. designed trolley and hoist. The Ederer single-failure-proof design is described in Revision 3, Amendment 3, to Generic Licensing topical Report EDR-1(P)-A, "Ederer Nuclear Safety-Related Extra Safety and monitoring (X-SAM) Cranes", dated October 8,1982. The report describes the design and testing of the single-failure-proof features which are included in Ederer's X-SAM cranes intended for handling spent fuel casks and other safety related loads in a nuclear power plant. NRC staff approval of the report was documented in a Safety Evaluation transmitted by NRC {{letter dated|date=August 26, 1983|text=letter dated August 26,1983}}. |
| Licensing NSP submitted the crane upgrade for approval to the NRC via letter dated October 4, 1991, as supplemented by letter dated December 16,1991. | | Licensing NSP submitted the crane upgrade for approval to the NRC via {{letter dated|date=October 4, 1991|text=letter dated October 4, 1991}}, as supplemented by {{letter dated|date=December 16, 1991|text=letter dated December 16,1991}}. |
| The NRC approved the license amendment request and issued License Amendment Nos. 99 and 92 to Facility Operating License Nos. DPR-42 and DPR-60 on July 9, 1992. | | The NRC approved the license amendment request and issued License Amendment Nos. 99 and 92 to Facility Operating License Nos. DPR-42 and DPR-60 on July 9, 1992. |
| As requested in the July 9,1992 approval, NSP submitted additional information to the NRC on January 25,1993. This information was reviewed and found acceptable by the NRC on May 3,1993. | | As requested in the July 9,1992 approval, NSP submitted additional information to the NRC on January 25,1993. This information was reviewed and found acceptable by the NRC on May 3,1993. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3371999-10-20020 October 1999 Forwards Notice of Docketing of License SNM-2506 Amend Application.Notice Has Been Forwarded to Ofc of Fr for Publication ML20217M1111999-10-19019 October 1999 Forwards Insp Repts 50-282/99-14 & 50-306/99-14 on 990920- 22.One Violation Noted & Being Treated as Ncv.Insp Focused on Testing & Maint of Heat Exchangers in High Risk Sys ML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20217C2351999-10-0606 October 1999 Forwards Insp Repts 50-282/99-12 & 50-306/99-12 on 990823-0917.No Violations Noted.Insp Consisted of Selected Exam of Procedures & Representative Records,Observation of Activities & Interviews with Personnel ML20212J8811999-09-28028 September 1999 Forwards Preliminary Accident Sequence Precurson Analysis of Operational Event That Occurred at Plant,Unit 1 on 990105, for Review & Comment.Comment Requested within 30 Days of Receipt of Ltr IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20212D8401999-09-16016 September 1999 Discusses 990902 Telcon Between D Wesphal & R Bailey Re Administeration of Retake Exam at Prairie Island During Wk of 991206.NRC May Make Exam Validation Visit to Facility During Wk of 991116 ML20217H2331999-09-10010 September 1999 Forwards Security Insp Repts 50-282/99-10 & 50-306/99-10 on 990809-12.Two Findings,Each of Low Risk Significance Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217H5661999-09-0909 September 1999 Discusses 990907 Pilot Plan Mgt Meeting Re Results to-date of Pilot Implementation of NRC Revised Reactor Oversight Process at Prairie Island & Quad Cities.Agenda & Handouts Provided by Utils Encl ML20212A9241999-09-0909 September 1999 Discusses Plans Made During 990902 Telephone Conversation to Inspect Licensed Operator Requalification Program at Prairie Island During Weeks of 991101 & 991108.Requests That Written Exams & Operating Tests Be Submitted by 991022 ML20212B0511999-09-0909 September 1999 Forwards Insp Repts 50-282/99-11 & 50-306/99-11 on 990816-20.One Issue of Low Safety Significance Was Identified & Being Treated as Ncb ML20211Q7641999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Plant Operator License Applicants During Wk of 000515,in Response to D Westphal ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211D3541999-08-24024 August 1999 Discusses GL 95-07 Re Pressure Locking & Thermal Binding of safety-related Power Operated Gate Valves.Forwards SE Re Response to GL 95-07 ML20211C7601999-08-19019 August 1999 Confirms NRC Intent to Meet with NSP & Ceco on 990807 in Lisle,Il to Discuss with Region III Pilot Plants,Any Observations,Feedback,Lessons Learned & Recommendations Relative to Implementation of Pilot Program ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20211B2621999-08-17017 August 1999 Forwards Insp Repts 50-282/99-09 & 50-306/99-09 on 990719-22.No Violations Noted.Insp Included Review & Evaluation of Current Emergency Preparedness Performance Indicators ML20211C7371999-08-17017 August 1999 Discusses Closure of Staff Review Re Generic Implication of Part Length Control Rod Drive Mechanism Housing Leak on 980123.Enclosed NRC 980811 & 1223 Ltrs Responded to WOG Positions Re Corrective Actions ML20210T5661999-08-12012 August 1999 Forwards RAI Re & Suppl ,which Requested Exemptions from TSs of Section III.G.2 of 10CFR50 App R,To Extent That Specifies Separation of Certain Redundant Safe Shutdown Circuits with fire-related Barriers ML20210R7021999-08-12012 August 1999 Forwards Insp Repts 50-282/99-06 & 50-306/99-06 on 990601- 0720.One NCV Occurred,Consistent with App C of Enforcement Policy ML20210P5191999-08-11011 August 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & NSP Responses for PINGP & 951117. Staff Reviewed Info in Rvid & Released Info as Rvid Version 2.Requests Submittal of Comments Re Revised Rvid by 990901 ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209J0941999-07-15015 July 1999 Forwards SER Finding Rev 7 to Topical Rept NSPNAD-8102, Reload Safety Evaluation Methods for Application to PI Units, Acceptable for Ref in Plant Licensing Actions ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209H8361999-07-0202 July 1999 Forwards Operator Licensing Exam Repts 50-282/99-301(OL) & 50-306/99-301(OL) for Tests Administered During Week of 990517-21.Two Applicants Passed All Sections of Exam & Issued Reactor Operator Licenses to Operate Pings ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209F0391999-06-30030 June 1999 Forwards Insp Repts 50-282/99-04 & 50-306/99-04 on 990407-0531.Violation Noted.Notice of Violation or Civil Penalty Will Not Be Issued,Based on NRC Listed Decision to Exercise Discretion ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20196D5501999-06-18018 June 1999 Forwards Individual Exam Results for Licensee Applicants Who Took May 1999 Initial License Exam.In Accordance with 10CFR2.790,info Considered, Proprietary. Without Encls ML20196A6741999-06-17017 June 1999 Refers to 990517-20 Meeting with Util in Welch,Minnesota Re Licensee Initiatives in Risk Area & to Establish Dialog Between SRAs & Licensee PRA Staff 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F4331999-10-15015 October 1999 Forwards Rev 39 to Security Plan.Changes Do Not Decrease Effectiveness of Security Plan.Rev Withheld,Per 10CFR73.21 ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212F5121999-09-20020 September 1999 Forwards Response to NRC , Preparation & Scheduling of Operator Licensing Examinations ML20211N8631999-09-0707 September 1999 Withdraws 970814 Request for Exemption from 10CFR50,App R, Section III.G.2, Fire Protection of Safe Shutdown Capabilities ML20211K5911999-09-0101 September 1999 Informs That Util Reviewed Rvid Data Base,As Requested in NRC .Summary of Proposed Changes & Observed Differences Are Included in Encl Tables ML20211L0211999-09-0101 September 1999 Provides Notification That License Amends 141 & 132 & Associated License Conditions 6 & 7 Have Been Fully Implemented ML20211Q6041999-08-31031 August 1999 Forwards Rev 19 to USAR for Pingp,Per 10CFR50.71(e).Rev Brings USAR up-to-date as of 990228,though Some Info Is More Recent.Attachment 1 Contains Descriptions & Summaries of SE for Changes,Tests & Experiments,Per 10CFR50.59 ML20211K5931999-08-31031 August 1999 Forwards License Amend Request for License SNM-2506, Proposing Change to License Conditions 6,7 & 8 & TSs App a of License by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211C2311999-08-19019 August 1999 Forwards Unit 1 ISI Summary Rept,Interval 3,Period 2 Refueling Outage Dates 990425-0526,Cycle 19 971212-990526. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarizes Results ML20211B8311999-08-19019 August 1999 Forwards Request for Relief 8 Re Limited Exams Associated with Unit 1 Third ten-year Interval Inservice Insp Program. Licensee Requests Relief Due to Impractibility of Obtaining 100% Exam Coverage for Affected Items ML20211B5711999-08-19019 August 1999 Forwards Second 90-day Rept for Implementation of Voltage Based Repair Criteria at Prairie Island Unit 1.Rept Fulfills Requirements of Section 6.b of Attachment 1 to GL 95-05 ML20211B0561999-08-18018 August 1999 Provides Addl Info on Proposed Rev to Main Steam Line Break Methodology ,in Response to NRC Staff Request Made in 990416 Telcon.Nuclear Svcs Corp Rept PIO-01-06, Analysis Rept Structural Analyses of Main Steam Check... Encl ML20210G5061999-07-30030 July 1999 Responds to Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates 05000282/LER-1999-007, Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics1999-07-23023 July 1999 Forwards LER 99-007-00,re Loss of CR Special Ventilation Function.One New Commitment Was Made in Rept as Indicated in Corrective Action Section Statement in Bold Italics ML20210J4991999-07-22022 July 1999 Forwards Rev 18 to USAR for Pingp,Bringing USAR up-to-date as of 990228,though Some Info More Recent.Safety Evaluation Summaries Also Encl ML20209H8051999-07-14014 July 1999 Forwards Summary of non-modification Safety Evaluation Number 515 Re Storage of Fuel Inserts,Per Insp Rept 72-0010/99-201 ML20209D4181999-07-0707 July 1999 Informs That Util Has Changed Listed TS Bases Pages Attached for NRC Use.Util Made No New Commitments in Ltr ML20209C3951999-07-0101 July 1999 Forwards Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20209B7541999-07-0101 July 1999 Final Response to GL 98-01,Suppl 1 Re Y2K Readiness of Computer Sys.Sys Remediated as Required for Plant Operation. Contingency Plans Developed to Mitigate Impact of Y2K-induced Events at Key Rollover Dates ML20196J8941999-06-30030 June 1999 Transmits Util Comments on Draft Regulatory Guide DG-1074, Steam Generator Tube Integrity. Licensee Recommends That NRC Focus on Several Important Listed Areas Considered Principal Concerns & Contentions ML20209C3011999-06-29029 June 1999 Forwards Annual Rept of Corrections to NSP ECCS Evaluation Models,Iaw 10CFR50.46.Since All Analyses Remain in Compliance,No Reanalysis Is Required or Planned ML20209B5751999-06-24024 June 1999 Submits Revised Relief Request for Limited Examinations Associated with Third 10-yr ISI Examination Plan.Attached Is Unit 1 Relief Request 7,rev 1 Which Addresses Limited Examinations ML20196F3871999-06-23023 June 1999 Forwards Revised Pages 71,72 & 298 of Rev 7 to NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units, Per Discussions with Nrc.Approved Version of Rept Will Be Issued 05000282/LER-1999-006, Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics1999-06-18018 June 1999 Forwards LER 99-006-00 Re Discovery That Manual SI Actuation Switch Had Not Been Tested on Staggered Basis During Integrated SI Test.Two New Commitments Are Indicated in Corrective Action Section Statement in Bold Italics ML20195G4281999-06-0909 June 1999 Notifies That Amsac/Dss Mods Completed & TS 138/129 Has Been Fully Implemented 05000282/LER-1999-005, Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved1999-06-0707 June 1999 Forwards LER 99-005-00 Re Containment Inservice Purge Sys Not Isolated During Heavy Load Movement Over Fuel.Event Has Indicated That Level of Performance Expected by Mgt Has Not Yet Been Achieved ML20207F4301999-06-0101 June 1999 Forwards 1999 Unit 1 SG Insp Results,Per TS 4.12.E.1. Following Insp 84 Tubes Were Plugged for First Time ML20196L2461999-05-21021 May 1999 Forwards Rev 0 to COLR for Pingp,Unit 1 Cycle 20, IAW TS Section 6.7.A.6 ML20195C6861999-05-21021 May 1999 Forwards Rev 17 to USAR for Prairie Island Nuclear Generating Plant.Attachment 1 Contains Descriptions & Summaries of SEs for Changes,Tests & Experiments Made Under Provisions of 10CFR50.59 During Period Since Last Update ML20206U6781999-05-17017 May 1999 Forwards Revised Emergency Response Plan Implementing Procedures,Including Rev 15 to F3-3,rev 15 to F3-16,rev 14 to F3-22 & Table of Contents ML20206U7131999-05-17017 May 1999 Forwards Revised EOF Emergency Plan Implementing Procedures, Including Table of Contents & Rev 2 to F8-10, Record Keeping in Eof. with Updating Instructions ML20206T2461999-05-17017 May 1999 Forwards Off-Site Radiation Dose Assessment for Jan-Dec 1998, Rev 0 to Annual Radiactive Effluent Rept for 980105- 990103 & Effluent & Waste Disposal Annual Rept Solid Waste & Irradiated Fuel Shipments,Jan-Dec 1998 ML20206R0401999-05-13013 May 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Removing Plant Organization Requirement,Imposed in Amend 141/132 That Plant Manager,Who Has Responsibility for Overall Safe Operation of Plant,Report to Corporate Officer ML20206Q0871999-05-13013 May 1999 Forwards Result of Evaluation Re Ultrasonic Exams of SG Number 22 Performed in Accordance with ASME Boiler & Pressure Vessel Code Section Xi.Procedure Used for Evaluation Contained in WCAP-14166,submitted for Review ML20206F9381999-05-0303 May 1999 Forwards Response to NRC 990304 RAI Re GL 96-05 Program at Pingp.Licensee Commitments Are Identified in Encl as Statements in Italics ML20206J3851999-05-0303 May 1999 Forwards 1998 Annual Radiological Environmental Monitoring Rept 05000282/LER-1999-004, Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics1999-05-0303 May 1999 Forwards LER 99-004-00 Re Discovery of Inadequate Sp That Demonstrates Operability of SFP Special Ventilation Sys.Two New NRC Commitments Are Contained in Corrective Action Section of Rept in Bold Italics ML20206E1761999-04-28028 April 1999 Forwards Revised TS Pages for Amends 144 & 135 to Licenses DPR-42 & DPR-60,respectively,to Update Controlled Manual or File ML20205S3221999-04-20020 April 1999 Forwards Application for Amends to Licenses DPR-42 & DPR-60, Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements of TS 5.1 ML20205P9891999-04-12012 April 1999 Requests Approval for Proposed Alternatives to Liquid Penetrant Requirements of N-518.4 of 1968 ASME Boiler & Pressure Vessel Code.Results of Analysis & Summary of Tests Performed & Tests Results Are Encl ML20205Q0191999-04-12012 April 1999 Forwards Application for Amend to License DPR-42 & DPR-60, Relocating Shutdown Margin Requirements from TS to COLR 05000282/LER-1998-010, Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER1999-04-0808 April 1999 Forwards LER 98-010-01 Re Discovery That 32 App R Related MOVs Are Susceptible to Physical Damage by Fire Induced Hot Shorts.Rept Provides Addl Details on Current Plans for Completing C/As Committed to in Original LER ML20205P9221999-04-0101 April 1999 Submits Relief Request 8,rev 0 Which Addresses Limited Exams Associated with Unit 2 Third ten-year Interval Inservice Insp Program.Util Requests Relief Per 10CFR50.55a(q)(5)(iii) Due to Impracticality of Obtaining 100% Exam Coverage ML20205E8371999-03-31031 March 1999 Submits Four Copies of Rev 38 to Prairie Island Security Plan,Per 10CFR50.54(p).Changes Do Not Decrease Effectiveness of Security Plan.Encl Withheld,Per 10CFR73.21 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205Q5051999-03-30030 March 1999 Forwards Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327- 981229. Rept Identifies Components Examined,Exam Methods Used,Exam Number & Summarized Results ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20204H3371999-03-19019 March 1999 Forwards Application for Amend to Licenses DPR-42 & DPR-60, Removing Dates of Two NRC SERs & Correcting Date of One SER Listed in Section 2.C.4, Fire Protection 1999-09-07
[Table view] |
Text
Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 May 13,1996 NRC Dulletin 96-02 l
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U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 Response to NRC Bulletin 96-02 Movement of Heavy Loads over Spent Fuel, over Fuelin the Reactor Core. or over Safetv-Related Eauioment NRC Bulletin 96-02 requeste,d a review of our plans and capabilities for handling heavy loads. Attached is our report outlining the results of our review to date. The detailed review has not been completed as we discuss in the attachment but will be completed expeditiously.
In this letter we have made new Nuclear Regulatory Commission commitments indicated as the italicized statements in the attachment.
Please contact Jack Leveille (612-388-1121, Ext. 4662) if you have any questions related to this letter.
Aft Michael D Wadley Plant Manager Prairie Island Nuclear Generating Plant c: (see next page) 9605170192 960513 DR ADOCK 0500 2 ,
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i USNRC* NORTHERN STATES POWiR COMPANY
, May 13,1996
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- Regional Administrator - Region Ill, NRC
- Senior Resident inspector, NRC
! NRR Project Manager, NRC l J E Silberg i
, Attachments:
- 1. Affidavit i
- 2. Response to NRC Bulletin 96-02 4 l i
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I B9602-0 DOC
4 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO. 50-282 50-306 BULLETIN 96-02, MOVEMENT OF HEAVY LOADS OVER SPENT FUEL, OVER FUEL IN THE REACTOR CORE, OR OVER SAFETY-RELATED EQUIPMENT Northern States Power Company, a Minnesota corporation, with this letter is submitting information requested by NRC Bulletin 96-02.
This letter contains no restricted or other defense information.
NORTHERN STATES POWER COMPANY BY r M Michael D Wadley Plant Manager [L Prairie Island Nuclear Gendfating Plant On this y of before me a notary public in and for said County, personally appeared hlicfi%el D Wadley, Plant Manager, Prairie Island Nuclear Generating Plant; and being first duly swom acknow edged that he is authorized to execute this document on behalf of Northem States Power Company, that he knows the contents thereof, and that to the best of his knowledge, information, and belief e state de in it are e and that it is not interposed for delay.
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MARCIA K. LaCORE
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]a RESPONSE TO NRC BULLETIN 96-02 4
3 Bulletin 30-dav Reauired Resoonse:
1 For licensees planning to implement activities involving the handling of heavy j loads over spent fuel, fuel in the reactor core, or safety-related equipment within 4
the next 2 years from the date of this bulletin, provide the following:
l e A report, within 30 days of the date of this bulletin, that addresses the licensee's review of its plans and capabilities to handle heavy loads while the d
i reactor is at power (in all modes other than cold shutdown, refueling, and defueled) in accordance with existing regulatory guidelines. The report should also indicate whether the activities are within the licensing basis and
! should include, if necessary, a schedule for submission of a license j amendment request. Additionally, the report should indicate whether changes to Technical Specification will be required.
l-l PRAIRIE ISLAND REPORT:
! Our Configuration Management group prepared a " Heavy Loads" Design Basis
] Document (HL DBD) document in 1990 which evaluated the design and licensing l j criteria against the plant configuration and administrative processes. Discrepancies j found during this process were dispositioned in accordance with the Configuration Management procedures. The initial DBD was verified in depth (in 1990). The '
] objectives of the verification were to verify that: (1) design bases information pertaining i
- to the Heavy Loads Program was accurately reflected in Revision 0 of the HL DBD, (2)
!' the implementation of the HL Program conforms to NRC requirements and NSP commitments, and (3) sufficient programmatic controls are in place to ensure continual j compliance with reguir' 7 requirements and NSP commitments.
- Since 1990, the DBD has been revised twice. These revisions have focused on the 1 changes that have taken place since the initial issuance of the HL DBD (e.g., upgrading the auxiliary building crane for the handling of spent fuel storage casks) and have not j re-verified the details which were verified in depth in 1990. For the review requested by i this bulletin, we are performing a verification in depth.
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! To date, we have performed the requested review to a level of detail to allow us to provide a response to the request for information with a reasonable level of assurance ,
] of its accuracy. Since the review has not been completed to the level of detail that we '
! deem prudent (due to the resources necessary to complete such a review end the short
- reporting schedule specified in the bulletin), we will continue the review of ourheavy
- loads handling against the rsgulatory guidance and ourlicensing basis and
) communicate the results of the review.
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Attachment 2
- May 13,1996 Page 2 We have determined that, heavy loads are handled as described in the correspondence between the NRC and NSP in response to the December 22,1980 letter from Darrell Eisenhut, Director of Licensing, NRR, to all licensees of operating plants, titled " Control of Heavy Loads" with two notable differences.
- 1. The Prairie Island auxiliary building crane was upgraded to meet the single-failure-proof criteria of Section 5.1.6 and Appendix C of NUREG-0612 in anticipation of handling spent fuel dry storage casks. Prior to handling the first dry storage cask, submittals to the NRC in support of Technical Specification changes regarding the use of the upgraded crane were made (see details starting on page 3).
- 2. A construction gantry crane can be temporarily installed for the purpose of installing or removing temporary spent fuel storage racks in Pool #1. The heavy load handling considerations utilizing this crane has been discussed in docketed correspondence with respect to a fuel pool re-rack modification. This correspondence occurred at roughly the same time period as that of the generic heavy load issue discussions. Since, at the time, this crane was thought of as temporary (just to be used during these modifications) it was never considered during our responses to the generic issues. In fact, the temporary racks were removed once using this crane and utilizing the heavy loads handling process reviewed by the NRC for the re-rack project. Also, the racks were installed and removed once using the upgraded auxiliary building crane. During this evolution, the rack movements were controlled by procedures which met heavy loads handling generic requirements but the rack movements have not been incorporated into the formal plant heavy loads handling program. Therefore, we need to determine the compliance of our use of the gantry crane with all aspects of NUREG-0612 and incorporate these potential movements into the plant heavy loads handling program. We will ensure compliance with NUREG-0612, Section 5.1 pnor to the next use of the gantry crane within the spent fuelpool enclosure or submit correspondence detailing any necessary exception and its basis.
Licensing Basis Our review to date has determined that we are in compliance with our current licensing basis with the exceptions of two Updated Safety Analysis Repoit (USAR) mis-statements. One mis-statement is of the plant configuration with respect to the clearance above the spent fuel pool enclosure roof and the auxiliary building crane. The other error is the weight given for the spent fuel pool protective covers; the USAR states a weight of 3700 pounds per cover (which is the weight that the design drawing designated) whereas the weight has been determined to be 4550 pounds. These mis-statements do not affect our compliance with NUREG-0612 and we anticipate correcting the errors through the 10CFR50.59 process.
B9602-0. DOC
Attachment 2
- Technical Soecifications i
- In addition, our review has determined that no Technical Specification changes will be j required.
License Amendment Reauests 1
Because the discrepancies are likely remedied through the 50.50 process and there are l no Technical Specification changes required, no license amendment requests need to be submitted.
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Attachment 2
! , . May 13,1996 Page 4 Details regarding the upgraded auxiliary building crane follow:
Prairie Island Cask Handling System j Design in preparation for the dry cask storage project, the Prairie Island auxiliary building crane was upgraded in 1992 to meet the single-failure-proof criteria of Section 5.1.6 and Appendix C of NUREG-0612. The upgrade involved replacement the existing trolley structure and hoist with an Ederer, Inc. designed trolley and hoist. The Ederer single-failure-proof design is described in Revision 3, Amendment 3, to Generic Licensing topical Report EDR-1(P)-A, "Ederer Nuclear Safety-Related Extra Safety and monitoring (X-SAM) Cranes", dated October 8,1982. The report describes the design and testing of the single-failure-proof features which are included in Ederer's X-SAM cranes intended for handling spent fuel casks and other safety related loads in a nuclear power plant. NRC staff approval of the report was documented in a Safety Evaluation transmitted by NRC letter dated August 26,1983.
Licensing NSP submitted the crane upgrade for approval to the NRC via letter dated October 4, 1991, as supplemented by letter dated December 16,1991.
The NRC approved the license amendment request and issued License Amendment Nos. 99 and 92 to Facility Operating License Nos. DPR-42 and DPR-60 on July 9, 1992.
As requested in the July 9,1992 approval, NSP submitted additional information to the NRC on January 25,1993. This information was reviewed and found acceptable by the NRC on May 3,1993.
In addition to the crane upgrade, the TN-40 cask and lifting system are designed to meet the single-failure proof requirements of NUREG-0612. The lift beam is designed, fabricated and tested in accordance with ANSI N14.6-1986. The cask trunnions are designed with an increased safety factor, as required by section 5.1.6 (3) of NUREG-0612.
The cask and lift beam design were reviewed as part of the dry cask storage Part 72 application. This cask design was approved and issued NRC license SNM-2506 on October 19,1993.
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Attachment 2 4 .
May 13,1996 Page 5 The pre-operationalload test of the cask trunnions was a subject of a separate NRC l l SER, dated June 12,1995.
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] NRC Pre-Ooerational Insoection i
j Cask and lift beam fabrication, as well as load handling procedures and practices were j reviewed by the NRC prior to initial cask loading during a special NRC inspection from j January 24 through May 11,1995. This inspection was documented in Inspection i Report 50-282/95002(DRP); 50-306/95002; 72-10/95002(DRP), June 30,1995. This l
3 inspection concluded:
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- The licensee satisfied all of the design and testing requirements specified in l established industry standards for the control of heavy loads, such as dry cask storage.
- Section 2 of this inspection report discussed the inspector's review of the Prairie island
- cask handling system, and included the areas of auxiliary building crane modification,
! post modification testing, load testing of th 9 TN-40 lift beam, load testing of the auxiliary )
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building crane, load testing of the cask trunnions, auxiliary building crane hook load test, cask transport vehicle route, special lifting device configuration, rated load of the
- auxiliary building crane, lid lift shank hook and rigging, NDE of the lid lifting bridle, and i cask handling in the spent fuel cool.
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